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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
D. D. Lisowski, T. C. Haskin, A. Tokuhiro, M. H. Anderson, M. L. Corradini
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 75-87
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16993
Articles are hosted by Taylor and Francis Online.
Recent design efforts have used the reactor cavity cooling system (RCCS) for passive decay heat removal in the Next Generation Nuclear Plant. Employing a series of riser tubes and cooling panels that line the containment walls, the RCCS can provide an ultimate heat sink for decay power removal from the system without the need for AC power. With vessel wall temperatures expected to reach 450°C, intuition suggests that radiation will be the dominant mode of heat transfer. However, the authors show that several factors can alter these modes; variations in cavity height, riser tube geometry, and vessel heat flux may have significant roles in the heat removal by the RCCS.The authors have constructed a one-quarter-scale water-cooled experimental facility at the University of Wisconsin-Madison that is based on available open literature of the General Atomics modular high-temperature gas-cooled reactor, with a three-riser tube and cooling panel test section representing a 5-deg slice of the full-scale design. Under prototypic heat flux conditions, a series of scoping tests with linear and asymmetrically skewed heating profiles were performed to investigate the split in flow distribution among the parallel channels. Numerical results, using RELAP5 models and FLUENT simulations, provide a comparison to experimental data sets and insight into the split among heat transfer modes present in the cavity.Application of these passive decay heat removal systems demands a pragmatic approach that can account for the irregularities and nonuniformities present in a real design. In areas of blocked views, such as near support structures and primary cooling pipes, convection can provide a mechanism to smooth the otherwise skewed radiative heat flux for heat transfer from the reactor pressure vessel walls to the cooling panels. Integral to the design of the RCCS, the cooling fins serve to protect the cavity wall while adding additional pathways for heat dissipation by conduction into the cooling tubes.